Operational Neutron Source

Abstract

The invention relates generally to nuclear engineering and more particularly to controlled reactor start-up. The invention improves reliability of an operational neutron source by creating additional safety barriers between the coolant and the source active part materials. The operational neutron source is designed as a steel enclosure housing an ampule containing antimony and beryllium with separate antimony and beryllium cavities positioned coaxially. The antimony is contained in the central enclosure made of a niobium-based alloy unreactive with antimony. A beryllium powder bed is located between the antimony enclosure and the ampule enclosure. The ampule enclosure is made of martensite-ferrite steel poorly reacting with beryllium. An upper gas collector is located above the ampule, which serves as a compensation volume collecting gaseous fission products. At the bottom, the ampule is supported by a reflector and a bottom gas collector. The gas collectors, reflector and washers are made of martensite-ferrite grade steel.

Description

CROSS-REFERENCE TO RELATED APPLICATIONS[0001]This application is a US 371 Application from PCT / RU2015 / 000839 filed Dec. 1, 2015, which claims priority to Russia Application 2014151527 filed Dec. 19, 2014, the technical disclosures of which are hereby incorporated herein by reference.FIELD OF THE INVENTION[0002]The invention relates to nuclear engineering and is designed for controlled reactor start-up by rising the reactor to the working power level after normal and abnormal shutdowns.BACKGROUND OF THE INVENTION[0003]In order to improve the reactor safety and its dynamic properties, as well as to reduce consequences of start-up reactivity accidents, it is feasible to implement engineering measures to prevent “blind” start-up, because in subcritical reactor the neutron flux is the only and the most important variable parameter at reactivity rise. The controlled start-up means the possibility to measure the neutron flux in the reactor core depending on the position of standard control...

AI Technical Summary

Benefits of technology

The invention helps to make ne neutron source more reliable and durable. It includes additional safety barriers to prevent leaks and failure of the neutron source. This makes it easier for the source to operate safely and reliably for a long time.

Problems solved by technology

The amount of neutrons generated in the core as a result of spontaneous uranium fission (˜2 103 n / s), is not sufficient to provide a controlled neutron flux in measuring chambers during the start.

Such designs are very large and occupy a considerable area in the core.

The shortage of this design is potential antimony melting during the source manufacture and operation, resulting in the stratification of the antimony-beryllium composition and source efficiency degradation.

The shortage of this design is also potential antimony melting during the source manufacture and operation, resulting in the stratification of the antimony-beryllium composition and source efficiency degradation.

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